1-20 of 74
Keywords: severe accident
Close
Follow your search
Access your saved searches in your account

Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A037, August 8–12, 2022
Paper No: ICONE29-92239
..., implementing a TCA programme during operation phase; improving Severe Accident Management Guidelines (SAMG) implementation approval process by adding “the point of entry to the use of SAMGs is reached” to reduce the time of SAMG implementation approval process. UK HPR1000 IVR severe accident...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022
Paper No: ICONE29-91505
... Abstract For an in-vessel retention strategy, severe accident analysis needs to be input the condition of loading on a core catcher based on physically compatible assumptions. This study has conducted event tree analyses emphasizing key phenomena in the lower plenum based on available...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022
Paper No: ICONE29-93244
.... sodium-cooled fast reactor severe accident core catcher debris bed coolability Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-93244 COOLABILITY EVALUATION OF THE DEBRIS BED ON CORE CATCHER IN A SODIUMCOOLED FAST...
Proceedings Papers

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A021, August 8–12, 2022
Paper No: ICONE29-91506
... Abstract Hydrogen may be released into the containment atmosphere of a nuclear power plant during a severe accident. Locally, high hydrogen volume fraction can be reached that can possibly cause fast deflagration or even detonation and put the integrity of the containment at risk...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A011, August 8–12, 2022
Paper No: ICONE29-91836
... Abstract The hydrogen risk in small steel containment is one of the most important safety problems of small modular reactor (SMR), effective measures need to be taken to mitigate the risk of high concentration hydrogen in a small free volume during severe accidents. In the early stage...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A007, August 8–12, 2022
Paper No: ICONE29-91550
... of severe accident in SFP and highlights the importance of accident management of SFP. As the fuel building has no three-barriers containing radioactive products like the reactor building and SFP has significantly larger fuel inventory, the potential consequences of severe accident (radioactive materials...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A021, August 8–12, 2022
Paper No: ICONE29-93467
... research reactor, studying the migration behavior of molten material. The result shows that the number of cracks in cladding has significant influence on migration. severe accident U-Al alloy fuels migration numerical simulation SPERT research reactor Proceedings of the 2022 29th International...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A009, August 8–12, 2022
Paper No: ICONE29-91730
... Abstract The complicated severe accident phenomena in typical Pressurized Water Reactor (PWR) Generation III may have a strong influence on source term release into environment and radiological consequence. The study on sensitivity analysis is beneficial to the identification of important...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A002, August 8–12, 2022
Paper No: ICONE29-89870
... Abstract In-vessel retention (IVR) is a widely adopted severe accident mitigation strategy in the advanced commercial PWRs. External water cooling on the outer surface of the reactor pressure vessel (RPV) is designed to efficiently remove the decay heat from the in-vessel corium...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A001, August 8–12, 2022
Paper No: ICONE29-89217
... Abstract Molten corium-concrete interaction is an important phenomenon in the late phase of severe accident, threatening the integrity of containment and might causing potential large release of radioactivity. A sensitivity and uncertainty analysis of MCCI under severe accident of a 1000 MW...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A018, August 8–12, 2022
Paper No: ICONE29-92736
... Abstract The core of the nuclear reactor will melt during severe accidents, which may damage the integrity of the reactor pressure vessel and containment, and release radioactive materials to the environment. The third-generation pressurized water reactor is equipped with severe accident...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A019, August 8–12, 2022
Paper No: ICONE29-92842
... Abstract Filtered containment venting system (FCVS) is used in some nuclear power plants to avoid containment overpressure failure and uncontrolled radioactive release in severe accidents. Currently the opening strategy is mainly based on the containment pressure, such as the design pressure...
Proceedings Papers

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A027, August 8–12, 2022
Paper No: ICONE29-91929
... Abstract Three severe nuclear power accidents (Fukushima accident, Chernobyl accident and Three Mile Island accident) have proved that human errors in the mitigation of severe accidents will exacerbate the deterioration of accidents and cause immeasurable consequences. Therefore...
Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A079, August 8–12, 2022
Paper No: ICONE29-92120
... with stokes number. The results of this research can be used to assist the validation of pool scrubbing model. severe accident pool scrubbing jet regime aerosol retention efficiency solubility Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022...
Topics: Aerosols
Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A025, August 8–12, 2022
Paper No: ICONE29-90448
... Abstract Pool scrubbing is one of the severe accidents (SA) countermeasures in nuclear power plants. In pool scrubbing, gas containing Fission Products (FPs) generated in the reactor during SA is passed through the pool water in the suppression chamber to move FPs into the pool water...
Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A083, August 8–12, 2022
Paper No: ICONE29-92167
... the coolant inventory and increase the core power density, which is not good for nuclear safety. Severe accident studies on large PWRs cannot be directly applied to small PWRs. Loss of coolant accident is one of the main inducements of reactor core melting, which needs to be focused on prevention...
Proceedings Papers

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A013, August 8–12, 2022
Paper No: ICONE29-91422
... as a Lagrangian method is attracting increasing attention in severe accident analysis. In this paper, we developed an MPS code for the corium behavior analysis with several additional models added: a heat transfer model for thermal conductivity and a phase change model for Solid-liquid conversion, an enthalpy...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A020, August 8–12, 2022
Paper No: ICONE29-92721
... Abstract The fission products released from the core fuel in severe accidents are mainly transported in the form of aerosols and exist in the gas phase in the containment. Once the containment fails, it will cause radioactive leakage. As an important mitigation measure for severe accidents...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A011, August 4–6, 2021
Paper No: ICONE28-64252
... Abstract The aerosol removal mechanism and capacity related to passive containment cooling system (PCS) for PWR reactors during the severe accident is an important and interesting topic among researchers, which can enhance the natural removal of suspended aerosols, reducing the radioactivity...